HIGH BURNUP FUEL TECHNOLOGY IN KOREA |
Song, Kun-Woo
(Korea Atomic Energy Research Institute)
Jeong, Yong-Hwan (Korea Atomic Energy Research Institute) Kim, Keon-Sik (Korea Atomic Energy Research Institute) Bang, Je-Geon (Korea Atomic Energy Research Institute) Chun, Tae-Hyun (Korea Atomic Energy Research Institute) Kim, Hyung-Kyu (Korea Atomic Energy Research Institute) Song, Kee-Nam (Korea Atomic Energy Research Institute) |
1 | Y.H. Jeong, H.G. Kim, D.J. Kim, B.K. Choi, J.H. Kim, 'Influence of Nb concentration in the -matrix on the corrosion behavior of Zr-xNb binary alloys', J. Nucl. Mater., 323, 72 (2003) DOI ScienceOn |
2 | V.F. Urbanic, R.W. Gilbert, 'Effect of microstructure on the corrosion of Zr-2.5%Nb alloys', Proc. of IAEA Technical Committee Meeting on Fundamental Aspects of Corrosion on Zirconium Based Alloys in Water Reactor Environments, International Atomic Energy Agency, Vienna, Italy, IWGFPT/34, p.262 (1990) |
3 | J.H. Kim, M.H. Lee, B. K. Choi, Y.H. Jeong, 'Deformation of Zircaloy-4 cladding during a LOCA transient up to 1200oC', Nucl. Eng. and Des., 234, 157 (2004) DOI ScienceOn |
4 | H. Assmann and H. Bairiot, process and Product Control of Oxide Powder and Pellets for Reactor Fuel Application, in: Guidebook on Quality Control of Water Reactor Fuel, Tech. Report Series No. 221, IAEA, Vienna (1983) |
5 | Y. Harada and S. Doi, J. Nucl. Sci. Technol., 35 (1998) 411 DOI |
6 | C.B. Lee, Y.S. Yang, 'INFRA Code Results of FUMEXII', IAEA CRP 'Improvement of models used for fuel behavior simulation (FUMEX-II), IAEA, Vienna, Dec. 5- 8, 2005 |
7 | D. H. Kim et al., 'Post-Irradiation Annealing Test of High Burnup Fuel', 2005 Water Reactor Fuel Performance Meeting, Kyoto, Japan, Oct. 2-6, 2005 |
8 | S. Ravel, et al., 'Partitoning of grain boundary and matrix gas inventories: Results obtained using the ADAGIO facility', Fission Gas Behavior in Water Reactor Fuels, Cadarache, France, 2002 |
9 | C.H. Shin, Y.J. Choo, S.K. Moon, S.Y. Chun, T.H. Chun, CHF Performance of a Hybrid Mixing vane Grid for Nuclear Fuel Bundle, Proc. 2007 Int. LWR Fuel Performance Mtg, San Francisco, Sep. 30-Oct. 3, 2007 |
10 | Y.W. Rhee, K.S. Kim, K.W. Song, Thermochimica Acta 455 (2007) 80 DOI ScienceOn |
11 | K.W. Song, K.S. Kim, K.W. Kang, et al., J. Korean Nucl. Soc. 31 (1999) 335 |
12 | Structural Dynamics Research Corporation, 2002, 'I-DEAS Master Series 9.0,' OH, USA |
13 | H.S. Kang, K.N. Song, K.H. Yoon, T.H. Chun, D.S. Oh, W.K. In, H.K. Kim, and Y.H. Jung, 'Grid with Nozzletype Coolant Deflecting Channels for Use in Nuclear Reactor Fuel Assemblies,' US Patent US 6130927, 2000 |
14 | Y. Harada, J. Nucl. Mater. 238 (1997) 237 |
15 | G.A. Wood and C.P. Perkins, in: Advances in Pellet Technology for Improved Performance at High Burnup, IAEA-TECDOC-1036, IAEA, Vienna, 1998, p. 49 |
16 | H.G. Kim, J.Y. Park, Y.H. Jeong, 'Phase boundary of the Zr-rich region in commercial grade Zr-Nb alloys', J. Nucl. Mater., 347, 140 (2005) DOI ScienceOn |
17 | J.A. Turnbull, J. Nucl. Mater. 50 (1974) 62 DOI ScienceOn |
18 | C.B. Lee, Y.S. Yang, Y.M. Kim, D.H. Kim, J.G. Bang, Y.H. Jung, 'High Burnup UO2 Fuel Rod Performance Code INFRA', Proc. of the 2004 International Meeting on LWR Fuel Performance, Orlando, Florida, Sep. 19-22, 2004 |
19 | C.B. Lee, D.H. Kim, Y.M. Kim, Y.S. Yang, S.K. Kim, Y.H. Jung, Y.B. Chun, H.S. Seo, E.P. Lee, H.K. Lee, H.M. Kwon. Y.H. Jung, D.K. Min, J.I. Kim, O.H. Kim, H.D. Chae, 'Post-irradiation Examination of High Burnup Fuel', Proc. of the 2004 International Meeting on LWR Fuel Performance, Orlando, Florida, Sep. 19-22, 2004 |
20 | H.S. Kang, K.N. Song, K.H. Yoon, T.H. Chun, D.S. Oh, W.K. In, H.K. Kim, and Y.H. Jung, 'Side-slotted Nozzle type Double Sheet Spacer Grid for Nuclear Fuel Assemblies,' US Patent US 6744843 B2, 2004 |
21 | Daum, R. S. et. al., 'On the Embrittlement of Zircaloy-4 Under RIA-Relevant Conditions' Zirconium in the Nuclear Industry : Thirteenth International Symposium, ASTM STP 1423, PA, pp. 702-719, 2002 |
22 | Y.H. Jeong. K.O. Lee, H.G. Kim, 'Correlation between microstructure and corrosion behavior of Zr-Nb binary alloys', J. Nucl. Mater., 302, 9 (2002) DOI ScienceOn |
23 | K.N. Song et al., 'Multydisplinary Design of the Spacer Grid Assembly for PWR,' IWMDE2006, Japan, 2006 |
24 | K.W. Song, K.S. Kim, K.W. Kang, Y.H. Jung, J. Nucl. Mater. 317 (2003) 204 DOI ScienceOn |
25 | K.H. Yoon, K.N. Song, T.H. Chun, D.S. Oh, W.K. In, H.K. Kim, H.S. Kang, and Y.H. Jung, 'Spacer Grid with H-spring for Fuel Rods for Use in Nuclear Reactor Fuel Assemblies,' US Patent US 6167105, 2000 |
26 | Frick et al., 'Overview on the Development and Implement of Methodologies to Compute Vibration and Wear of Steam Generator Tubes,' Symposium on Flow Induced Vibration: Vol. 3, Vibration in Heat Exchanger, pp. 149-161, 1984 |
27 | H.G. Kim, Y.H. Jeong, T.H. Kim, 'Effect of phase, precipitate and Nb-concentration in matrix on corrosion and oxide characteristics of Zr-xNb alloys', J. Nucl. Mater., 317, 1 (2003) DOI ScienceOn |
28 | V.F. Urbanic, B.D. Warr, A. Manolescu, C.K. Chow, M.W. Shanahan, 'Oxidation and deuterium uptake of Zr-2.5Nb pressure tube in CANDU-PHW reactors', Zirconium in the Nuclear Industry, ASTM STP 1023, 20 (1989) |
29 | J.B. Ainscough, F. Rigby, S.C. Osborn, J. Nucl. Mater. 52 (1974) 191 DOI ScienceOn |
30 | J.Y. Park, B.K. Choi, Y.H. Jeong, Y.H. Jung, 'Corrosion behavior of Zr alloys with a high Nb content', J. Nucl. Mater., 340, 237 (2005) DOI ScienceOn |
31 | Vishay Measurements Group Inc., 2001, ' User's Manual,' CT, USA |
32 | J.H. Kim, M.H. Lee, B. K. Choi, Y.H. Jeong, 'Deformation and thermal quench behavior of HANA cladding in LOCA condition', Proc. of 2005 Water Reactor Fuel Performance Meeting, Kyoto, Japan, Oct. 2-6, p.178 (2005) |
33 | B.E. Ingleby, K. Hand, in: c, Advances in Ceramics vol. 17, I.J. Hastings (eds), Amer. Ceramic Soc., 1986, p. 57 |
34 | K.H. Yoon, K.N. Song, T.H. Chun, D.S. Oh, W.K. In, H.K. Kim, H.S. Kang, and Y.H. Jung, 'Spacer Grid for Nuclear Fuel Assemblies with Grid Springs Maintaining Conformal Contact with Fuel Rods and Enlarged Elastic Range,' US Patent US 6707872 B2, 2004 |
35 | Averty, X. et. al., 'Tensile tests on ring specimens machined in M5 cladding irradiated 6 cycles' IRSN 2003/50, 2003 |
36 | L. Bourgeois, Ph. Dehaudt, C. Lemaignam, et al., J. Nucl. Mater. 297 (2001) 313 DOI ScienceOn |
37 | S.H. Lee, J.Y. Kim, and K.N. Song, Design Improvement of an OPT-H Type Nuclear Fuel Rod Support Grid by Using an Axiomatic Design and an Optimization, Journal of Mechanical Science and Technology, Vol. 21, pp.1191- 1195, 2007 과학기술학회마을 DOI |